• 품질경영학회지
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• 제43권3호
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• pp.239-252
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• 2015

Purpose: Lead has been widely used in radiation shielding for its low price and high workability. Recently in several europe countries, use of lead was banned for environmental issues. Also lead can cause health problems like alergies. Alternative materials for lead are highly required. The purpose of this study was to propose lead free radiation shielding material. Methods: Research of radiation shielding in Korea is not easy for certain limits such as radiation materials, experimental facilities and places. The collected data through the research were simulated using MCNPX. The simulation tools used for this study were utilized Monte Carlo method. Results: we suggest new design of lead free radiation shielding material using MCNPX code comparing shielding performance of new composite materials to lead. Conclusion: This newly introduced nano-scale composite of metal and polymer makes new chance for highly lightened radiation protective garments with endurable shielding performance.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1817-1825
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• 2020

Background: Cosmic ray-induced particles can lead to failure of semiconductors packaged for export during air transport. This work performed MCNP 6.2 simulations to optimize shielding against neutrons and protons induced by cosmic radiation Methods and materials: The energy spectra of protons and neutrons by incident angle at the flight altitude were determined using atmospheric cuboid model. Various candidates for the shielding materials and the geometry of the Unit Load Device Container were evaluated to determine the conditions that allow optimal shielding at all sides of the container. Results: It was found that neutrons and protons, at the flight altitude, generally travel with a downward trajectory especially for the particles with high energy. This indicated that the largest number of particles struck the top of the container. Furthermore, the simulation results showed that, among the materials tested, borated polyethylene and stainless steel were the most optimal shielding materials. The optimal shielding structure was also determined with the weight limit of the container in consideration. Conclusions: Under the determined optimal shielding conditions, a significantly reduced number of neutrons and protons reach the contents inside the container, which ultimately reduces the possibility of semiconductor failure during air transport.

• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3429-3439
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• 2022

The MCS code is a computer code developed by the Ulsan National Institute of Science and Technology (UNIST) for simulation and calculation of nuclear reactor systems based on the Monte Carlo method. The code is currently used to solve two main types of reactor physics problems, namely, criticality problems and radiation shielding problems. In this paper, the radiation shielding capability of the MCS code is validated by simulating some selected SINBAD (Shielding Integral Benchmark Archive and Database) experiments. The whole validation was performed in two ways. Firstly, the functionality and computational rationality of the MCS code was verified by comparing the simulation results with those of MCNP code. Secondly, the validity and computational accuracy of the MCS code was confirmed by comparing the simulation results with the experimental results of SINBAD. The simulation results of the MCS code are highly consistent with the those of the MCNP code, and they are within the 2σ error bound of the experiment results. It shows that the calculation results of the MCS code are reliable when simulating the radiation shielding problems.

• 대한방사선기술학회지:방사선기술과학
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• 제40권2호
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• pp.269-274
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• 2017

본 연구에서는 기존의 납을 대체할 수 있는 의료방사선 차폐시트 적용을 위해 몬테카를로 시뮬레이션을 이용하여 각각에 대한 원소별 차폐능을 모의 추정하였다. 원소들의 선정은 차폐성능이 큰 것으로 알려진 원자번호가 큰 원소와 금속원소를 중심으로 최근에는 다양한 복합재들이 차폐성능을 향상시킨다는 보고에 따라 경량화, 가공성, 활동성 등을 고려하여 21개 원소를 선정하였다. 몬테카를로 시뮬레이션 코드를 이용한 전산모사 투과도 실험으로 21개의 원소를 대상으로 시뮬레이션 하여 추정한 결과 납을 대체할 차폐물질로 적당한 원소의 투과율은 텅스텐(w) 98.82％, 가돌리늄(Gd) 92.96％, 주석(Sn) 86.87％, 인듐(In) 86.38％, 안티몬(Sb) 86.33％, 바륨(Ba) 78.51%로 평가되었으며, 각 원소별 차폐성능을 모의 추정한 결과 텅스텐과 금이 98.82%와 98.44%로 차폐율이 가장 높은 것으로 추정되었다. 경제성과 가공성을 고려할 때 위 원소를 화합한 물질로 차폐체를 만드는 것이 적절할 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제56권9호
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• pp.3545-3552
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• 2024

Polymers have become widely used substrate materials for shielding neutron rays because of their high hydrogen content and easy processing procedures. Rare-earth materials are also being gradually adopted as neutron absorbers because of their considerable thermal neutron absorption cross-sections. This paper utilizes the FLUKA Monte Carlo simulation program to compare the shielding effects of various polymers and rare-earth oxides on neutron rays across different energy ranges. The study investigates the superior shielding materials for neutron radiation in each energy range. Subsequently, a series of materials are simulated by combining the preferred shielding materials for neutron rays in each energy range, exploring the influence of material composition and composite structure on the effectiveness of neutron ray shielding. It is revealed that the preferred material for shielding neutron rays changes for different energy ranges. For low-energy neutron rays, rare-earth oxides such as Sm₂O₃ and Gd₂O₃ demonstrate the most effective shielding, whereas for high-energy neutron rays, polyethylene (PE) provides the best shielding performance. Materials with different compositions show varying preferred structures when dealing with a ²⁵²Cf neutron source. However, in mitigating the secondary gamma rays generated during the neutron shielding process, stacked-type materials exhibit the most effective shielding performance.

• 한국방사선학회논문지
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• 제11권5호
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• pp.329-334
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• 2017

본 연구는 의료방사선 차폐를 위해 의료 환경에 적합한 친환경 소재를 찾아 방사선 차폐 시트 제작의 가능성을 추정하고자 하는 것이다. 현재 차폐 소재로 주로 사용되는 납을 대신한 텅스텐 제품이 많이 있으나, 경제성으로 인해 경량의 차폐 시트의 대량생산에는 다소 문제가 있다. 이러한 문제점을 해결하기 위해 경제성 있는 경량 친환경 소재를 필요로 한다. 이러한 소재로써 본 연구에서는 황산바륨과 요오드를 제안하였다. 두 물질은 방사선 촬영에서 이미 조영제로 사용되고 있어 방사선을 흡수하는 특성으로 차폐 재료로써 일정 영역에서 충분히 차폐효과가 있을 것으로 예측하고 있다. 따라서 본 연구에서는 방사선 차폐 재료로 검증하기 위해 몬테카를로 시뮬레이션을 이용하여 모의 추정하였다. 황산바륨과 요오드 등 조영제인 경우 고에너지 영역에서 방사선 흡수효과가 크게 나타나, 의료방사선 고관전압 촬영영역 120 kV의 두께별 에너지영역에서 두 차폐물질의 유효성을 평가하였다. 모의 추정 결과 두 물질 모두 차폐의 유효성을 추정할 수 있었다. 요오드가 황산바륨보다 차폐효과 높았으며, 0.05mm 두께에서는 효과성이 크게 나타났다. 따라서 방사선차폐 시트의 제작 재료로 방사선 조영제인 요오드도 황산바륨과 같이 가능하다는 것을 몬데카를로 시뮬레이션을 통해 확인 할 수 있다.

• 대한방사선기술학회지:방사선기술과학
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• 제37권2호
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• pp.143-150
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• 2014

몬테칼로 모사를 이용하여 베타선으로부터 발생되는 제동복사선과 이로 인해 받는 선량을 비교 분석 하고자 하였으며, 방사선 차폐에 이용하는 납치마를 이용하여 실제 I-131 치료병실에서 발생되는 방사선의 감쇠정도를 비교하고자 하였다. 몬테칼로 모사를 이용하여 납 또는 물로 구성된 차폐체를 설정하여 베타선의 상호작용에 대한 스펙트럼을 분석하였으며, 납치마를 기준으로 0.25 mm 와 0.5 mm의 납 설정과 물 0.1 mm 와 0.2 mm를 설정하여 납만을 이용한 차폐방법과 물과 납을 두 가지를 이용한 차폐실험을 진행하였다. 실험 결과 납 두께 0.5 mm로 차폐 시 선량이 물과 납을 이용한 2차 차폐 방법을 사용했을 때와 유사하게 나타났으며, 납 0.25 mm 만을 사용했을 때 차폐효과가 다소 낮았지만, 납 차폐체가 없는 때의 선량에 비해 약 60% 감소효과를 나타냈다.

• Journal of Electrical Engineering and Technology
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• 제6권6호
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• pp.760-768
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• 2011

The performance of transmission lines and its shielding design during a lightning phenomenon are quite essential in the maintenance of a reliable power supply to consumers. The leader progression model, as an advanced approach, has been recently developed to calculate the shielding failure rate (SFR) of transmission lines using geometrical data and physical behavior of upward and downward lightning leaders. However, such method is quite time consuming. In the present paper, an effective method that utilizes artificial neural networks (ANNs) to create a metamodel for calculating the SFR of a transmission line based on shielding angle and height is introduced. The results of investigations on a real case study reveal that, through proper selection of an ANN structure and good training, the ANN prediction is very close to the result of the detailed simulation, whereas the Processing time is by far lower than that of the detailed model.

• 대한전기학회논문지:전력기술부문A
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• 제50권8호
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• pp.359-364
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• 2001

This paper presents the influence of the lightning overvoltage and the shielding effect of lightning arresters and overhead grounding wires on the DC railroad systems. Modeling of railroad system is established in ATPDraw to perform the simulation and the line constants of railroad were calculated using ATP_LCC. When a direct lightning strikes to the DC railroad, the result of simulation reveals that the shielding effect of arresters is reduced at messenger, trolly-wire, and the shielding effects of overhead grounding wire is over 90% than the case which does not include it. Therefore it is evaluated that overhead grounding wires should be installed in the DC railroad line.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2361-2369
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• 2020

Compton cameras using large scintillators have been developed for high imaging sensitivity. These scintillator-based Compton cameras, however, mainly due to relatively low energy resolution, suffer from undesired background-radiation signals, especially when radioactive materials' activity is very low or their location is far from the Compton camera. To alleviate this problem for a large-size Compton camera, in the present study, a hybrid-type shielding system was designed that combines an active shield with a veto detector and a passive shield that surrounds the active shield. Then, the performance of the hybrid shielding system was predicted, by Monte Carlo radiation transport simulation using Geant4, in terms of minimum detectable activity (MDA), signal-to-noise ratio (SNR), and image resolution. Our simulation results show that, for the most cases, the hybrid shielding system significantly improves the performance of the large-size Compton camera. For the cases investigated in the present study, the use of the shielding system decreased the MDA by about 1.4, 1.6, and 1.3 times, increased the SNR by 1.2-1.9, 1.1-1.7, and 1.3-2.1 times, and improved the image resolution (i.e., reduced the FWHM) by 7-8, 1-6, and 3-5% for ¹³⁷Cs, ⁶⁰Co, and ¹³¹I point source located at 1-5 m from the imaging system, respectively.